Can we tend the fire?

Can we tend the fire? Three lectures course on plasma surface interaction and edge physics I Introduction: WHAT happens in a fusion plasma near the walls Detlev Reiter Forschungszentrum Jülich GmbH, Institut für Energieforschung-4 52425 Jülich, Germany Thanks to: V. Philipps, A. Kirschner, R. Janev Forschungszentrum Jülich in der Helmholtz-Gemeinschaft Joint ICTP-IAEA Workshop on Atomic and Molecular Data for Fusion, Trieste 20-30 April 2009

Mankind learning to tend a fire, again. Fire from processes in atomic shell Fire from processes in atomic nucleus 100.000 years later. Chemical process: C x H y.+o 2 + CO z + H 2 O+ Nuclear process: d + t He + n

The Energy source of the sun and the stars in the universe is: Nuclear Fusion The vision of nuclear fusion research: A miniatur star in a solid container Fusion Reactor: T=100 Mill. degrees The Sun: T=15 Mill. degrees in the center Much too cold! d + t He + n p + p d, d + p He 3, He 3 + He 3 He 4 + p + p, Reaction time 1/(n p <σv> fus )=t fus approx. 10 9 years

What these lectures are NOT about: Fusion reactor From Robert Zemeckis movie: Back to the future II

The correct way: a magnetic bottle Here: the JET Tokamak 2 meters

Euratom 26 Fusion Associations Joint construction of JET (1978) Euratom - CEA (1958) France Euratom ENEA (1960) Italy (incl. Malta) Euratom - IPP (1961) Germany Euratom - FOM (1962) The Netherlands Euratom - FZJ (1962) Germany Euratom - Belgian State Belgium (1969) (incl. Luxembourg) Euratom - RISØ (1973) Denmark Euratom UKAEA (1973) United Kingdom Euratom - VR (1976) Sweden Euratom - Conf. Suisse Switzerland (1979) Euratom - FZK (1982) Germany Euratom CIEMAT (1986) Spain Euratom IST (1990) Portugal Euratom - TEKES (1995) Finland (incl. Estonia) Euratom - DCU (1996) Ireland Euratom - ÖAW (1996) Austria Eur - Hellenic Rep (1999) Greece (incl. Cyprus) Euratom - IPP.CR (1999) Czech Rep. Euratom - HAS (1999) Hungary Euratom MEdC (1999) Romania Euratom Univ. Latvia Latvia (2002) Euratom - IPPLM (2005) Poland Euratom - MHEST (2005) Slovenia Euratom CU (2007) Slovakia Euratom INRNE (2007) Bulgaria Euratom LEI (2007) Lithuania

FZ Jülich: in Germany fusion research is organized in the Helmholtz Association Germany Helmholtz Association DFG / Universities Europe Trilateral Euregio Cluster (B, Nl, Jül) EURATOM Association EFDA (JET, Technol.) F4E (ITER) HGF World IEA Implementing Agreement Plasma-Wall Interaction (J, USA, Canada) ITPA International Expert Groups TEXTOR

Hermann Ludwig Ferdinand von Helmholtz (1821-1894) 1847: precise formulation of the law of conservation of energy 1881: inclusion of chemical processes, free energy, internal energy Problem: what is the source of energy of the sun? how old is the sun? how old is the earth at highest? 1854: Theory of Contraction (together with: Lord Kelvin) The energy radiated by the sun is provided by contraction of the sun (and the stars), freeing the graviational energy, i.e. accounted for in a purely mechanical concept Age of the planet earth: ~ 10 Mill. Years (at highest)

Ca. 1925: Sir Arthur Eddington : Nuclear Fusion as energy source of the sun and the stars (E=m c 2 ) Ca. 1935: Hans Bethe und Carl Friedrich von Weizsäcker: final resolution of the nuclear fusion processes in the sun ( Bethe- Weizsäcker cycle ) (age of sun and earth: 4-5 billion years well possible)

1933: Oliphant und Rutherford fuse Deuteron atoms, discovery of tritium

L. Spitzer A proposed stellarator AEC Report No. NYO-993 (PM-S-1) 1951 US Fusions-Projekt: Matterhorn Known in those days: Only magnetic fields can confine the flame (Lasers did not yet exist) It has to be a toroidal configuration (H. Poincare, ~1880) The B-field has to be helical then: only a stellarator is possible Lyman Spitzer Inventing the stellarator -1968 : all expectations have been frustrated. All experiments have been gigantic (and costly) failures (Instabilities, sensitivity to small field errors,.) The final end of nuclear fusion research? No: a few small experiments in the USSR have shown surprising successes: Tokamaks

Progress in Tokamak research: Compare: Moore s Law mirco processors

Outline of course: Introduction: Fusion Research & Plasma-Wall Interaction I.) WHAT : basic plasma-wall interaction processes II.) HOW : can we make the application work? ITER III.) WHY : understanding the edge plasma, A&M processes Forschungszentrum Jülich in der Helmholtz-Gemeinschaft

Role of Edge Plasma Science Early days of magnetic fusion (sometimes still today?): Hope that a fusion plasma would not be strongly influenced by boundary: The edge region takes care of itself. Single goal: optimize fusion plasma performance Now: man made fusion plasmas are now powerful enough to be dangerous for the integrity of the container: The edge region does NOT take care of itself. It requires significant attention! The ITER lifetime, performance and availability will not only be influenced, it will be controlled by the edge region Forschungszentrum Jülich in der Helmholtz-Gemeinschaft

Role of Edge Plasma Science, cont. The layman s response to the idea: A miniature star (100 Mill degrees) in a solid container : THIS MUST BE IMPOSSIBLE! It turned out unfortunately (early 1990 th ): THE LAYMAN IS RIGHT! Almost... Forschungszentrum Jülich in der Helmholtz-Gemeinschaft

Atomic/Molecular processes, Plasma material interaction ITER Physics of hot plasma core Forschungszentrum Jülich in der Helmholtz-Gemeinschaft

Can we hope that magnetic confinement core plasma physics progress will mitigate plasma-surface problems? Candle, on earth Used air Candle, under mircogravity e.g.: parabola flight, g 0 Fresh air (only small, dim burn, at best) Convection, driven by buoyancy (i.e. gravity) Only Diffusion (no convection) Forschungszentrum Jülich in der Helmholtz-Gemeinschaft

Magnetic Fusion: how to produce convection? DIVERTOR I P I D I D I D Increase convection increase plasma surface interaction Forschungszentrum Jülich in der Helmholtz-Gemeinschaft

L. Spitzer A proposed stellarator, US Fusionsprojekt: Matterhorn AEC Report No. NYO-993 (PM-S-1) 1951 Lyman Spitzer Original report has two figures! To remove wall Released plasma Impurities already from the plasma boundary, by a magnetic exhaust The Divertor

JET (Joint European Torus) : Ø 8.5 m, 2.5 m high, 3.4 T, 7 MA, 1 min Key area for plasma wall interaction

Extrapolation: present experiments ITER Torus Axis Core: plasma similarity: present experiments are wind tunnel experiments for ITER A U G J E T I T E R Major Radius

Extrapolation of core plasma confinement to ITER ITER reference scenario Forschungszentrum Jülich in der Helmholtz-Gemeinschaft

Relative importance of plasma flow forces over chemistry and PWI I Plasma Core div(nv )+div(nv )= ionization/recombination/charge exchange Core (collisional +turbulent) cross field flow, D, V (advanced plasma scenario development) (empirical) ion transport scaling from spectroscopy on surface released impurities (interpretation, line shape modelling): Spectroscopy : nz* CR Model : nz* nz Transport Model : nz D, V

Relative importance of plasma flow forces over chemistry and PWI II edge region III divertor div(nv )+div(nv )= ionization/recombination/charge exchange II: midplain parallel vs. (turbulent) cross field flow III: target parallel vs. chemistry and PWI driven flow

Extrapolation: present experiments ITER Torus Axis Core: plasma similarity: present experiments are wind tunnel experiments for ITER Edge: Computational plasma edge modelling (lecture III) A U G J E T I T E R Major Radius Forschungszentrum Jülich in der Helmholtz-Gemeinschaft

Edge/divertor science interdisciplinary already a highly integrated field - plasma physics -CFD - rarefied gas dynamics - opacity - plasma wall interaction - atomic physics - molecular physics -... fusion, technical-, astro plasmas fluid-dynamics aero-dynamics, vacuum lighting, inertial fusion Atomic & Surface data (database: IAEA fusion data unit) this lecture I Forschungszentrum Jülich in der Helmholtz-Gemeinschaft

Plasma-wall interaction in fusion devices Impinging plasma and impurity particles - erosion of wall elements lifetime of wall elements is reduced - eroded wall particles can penetrate into core plasma dilution and radiation cooling of core plasma - re-deposition of eroded particles tritium retention in deposited layers (retained T has to be limited to 350g due to safety rule in ITER) Erosion, transport and redeposition of impurities is a crucial (show stopping?) issue in fusion research

Control of plasma-wall interaction: the limiter concept Limiter: A material piece protruding from the main wall intercept the closed field lines to extract power and particles. TEXTOR Toroidal belt pump limiter Poloidal limiters Poloidal limiter

Control of plasma-wall interaction: the divertor concept Divertor: A separate chamber in the vacuum vessel to which particles and energy are directed JET divertor

Next 2 slides: JUMPING AHEAD see again 3 rd lecture

Consequences for ITER design (B2-EIRENE): shift towards higher divertor gas pressure to maintain a given peak heat flux (Kotov et al., CPP, July 2006) ITER divertor engineering parameter: target heat flux vs. divertor gas pressure 1996 (ITER physics basis1999) 2003, neutral - neutral collisions.+ molecular kinetics (D 2 (v)+d +, MAR) 2005, + photon opacity P PFR : average neutral pressure in Private Flux Region ITER design review 2007-2009: Dome re-design now ongoing

Compare: re-entry problems e.g. Space shuttle) ~10 MW/m 2, for some minutes 10 MW/m 2 stationary: perhaps tolerable, but not trivial

Recycling Plasma - Wall Interactions Main plasma Boundary plasma Plasma impact e -, X n+,x 0 Reflection Scrape-off layer Re-deposition and co-deposition Retention Erosion n Solid Wall Material

Basic Processes Induced in Materials by Plasma Particle Impact Projectile, E o Implantation Vacancy Void Self-interstitial I-interstitial Reflection Dislocation Sputtering Energy dissipation by elastic (with atoms) and ineleastic (with electrons) collisions (10-13 sec, range 10-7 m, 200 ev D + ) Elastic collisons: Creation of vacancies and interstitials elastic collisions (energy transfer > threshold energy for damage) Diffusion of vacancies and interstitials voids, dislocations, swelling, radiation, embrittlement Sputtering of surface atoms (energy transfer > surface binding energy) Transmutation formation of nuclear reaction products (including H isotopes and He)

The 14 MeV fusion neutrons heat an external material (for energy conversion) and they breed Tritium in the blanket. Unfortunately: 14 MeV fusion neutrons also produce volumetric radiation damage, and change and deteriorate the material properties heat conductivity swelling ductility composition lattice defects scattering of phonons void formation, gas bubbles agglomeration of vacancies and helium neutron and helium induced embrittlement densification of dislocation network, agglomeration of helium bubbles on grain boundaries transmutation products Science of irradiated materials (not further discussed here)

Basic PSI Processes I.) Sublimation II.) Physical sputtering III.) Chemical erosion IV.) Radiation Enhanced Sublimation (RES) V.) Backscattering Only briefly discussed here: VI.) Retention (hydrogen isotopes) VII.) Desorption/Adsorption VIII.) Blistering IX.) Secondary electron emission Springer, 2005 Springer, 2006

I.) Sublimation

Power exhaust steady state heat loads Plasma input : Q (W/m 2 ) d Ts Armor material: thickness d with thermal conductivity λ Heat diffusion time t = d 2 /2D D= λ /ρ c D: diffusivity conductivity density heat capacity 4 s 5 10-5 m 2 /s In steady state Ts -Tw = Δ T = Q * d / λ Tw Q=10 MW/m 2, λ=200[w/(m K)], d=0.02m ΔT= 1000 C Water cooling Monoblock concept

Power exhaust transient heat loads (1) In transient events, like disruptions or ELMs, part of the plasma stored energy is deposited in very short pulses to the walls example: type I Elms in ITER: W thermal (Plasma) 350 MJ energy loss during ELM 2-6 % Energy per ELM deposition time 20 MJ (~30 hand grenades at 150g TNT each) 0.2 ms deposition area 10 m 2 power density 10 GW/m2

transient heat loads (2) In transient events the energy must be absorbed by the heat capacity ( inertial cooling ) T ( t) = P * ( 2 / π λ ρ c ) 0.5 * t 0.5 temperature power conductivity density heat capacity t = 0.25 ms Sublimation threshold: 2200 C Ts max = 6000 C Penetration depth: 0.15 mm Graphite Target will sublimate quickly With duration of 0.2 ms and area 10 m 2 the maximal energy per ELM in ITER must limited to < 1-2 % of stored energy to avoid material loss by sublimation Metals will melt leading to loss of melt layer by MHD effects in melt layer Type I ELM operation critical for ITER

Material Behaviour under Extreme Power Loads e- beam (120 kev) metals graphite, CFC Be: ca. 150 μ m W: ca. 10 µm homogeneous melting melt ejection boiling and droplet formation sublimation brittle destruction increasing energy density increasing energy density Effects of interaction FOR METALS: Splashing Formation of droplets Formation of dust FOR CARBON: Above a certain power load (threshold) emission of debris occurs = BRITTLE DESTRUCTION

MELTING observed commonly in present machines Limiter from FTU TZM coated with 2 mm VPS Tungsten Beryllium antenna screen at JET T m (Be) = 1278 o C TEXTOR: Melting of 170 mm B4C coating on copper

ASIDE: The TEXTOR PWI Test Facility with air lock a tool (user facility) for PWI research Air locks for PWI components < 15 cm diameter (enlargement foreseen) external heating (up to 1800K) or cooling (down to RT) radial movement (+- 5 cm around LCFS) rotatable electrical biasing of limiters exchange time for samples <½ day local gas injection systems TEXTOR PWI Test Facility viewing lines for diagnostics Comprehensive diagnostics overview spectroscopy (UV-VIS-IR) 2D imaging (Dα, CII etc.), high resolution spectroscopy laser-induced fluorescence 2D thermography, thermocouples colorimetry laser desorption/ablation edge diagnostics for ne, Te (Langmuir probes and atomic beams) Test Limiter inserted through air lock Presently used in cooperation with Japan (TEXTOR- IEA), VR, IPPWL, Slovenia, Universities,.

Inside the TEXTOR Tokamak @ FZ-Jülich

Focus on Plasma Surface interaction research

Plasma parameters at the TEXTOR PWI Test Facility: Exceeds ITER particle and heat fluxes parallel particle fluxes: up to 4 x10 24 /m 2 s particle fluencies: up to 2 10 26 /m 2 per day (150 s plasma per TEXTOR operation day ) parallel power fluxes: up to 200 MW/m 2 Melting of bulk W limiters in 4 sec 20 20

II.) Physical sputtering

Plasma-Wall Interaction Processes: Basic Processes II.) Physical sputtering Mechanism: energy transfer from projectile to solid atom at surface projectile D + collision cascade sputtered particle W 0 W Impinging projectile ion initiates collision cascade inside the solid energy transfer to surface solid atom which is released

Plasma-Wall Interaction Processes: Basic Processes II.) Physical sputtering Collision cascades: different regimes single collision regime linear cascade regime thermal spike regime Single collision: light ions at low energies, atomic motion stopped after few collisions, binary collision approximation (BCA) valid Linear cascade: collisions only between fast particles and atoms at rest, BCA Thermal spike: dense cascade, collisions between fast particles important

Plasma-Wall Interaction Processes: Basic Proceses II.) Physical sputtering Simulation of collision cascades: example linear cascade regime Monte Carlo simulation, Binary Collision Approximation 5 typical cascades of 3 kev Ar + ions into graphite Ion trajectory O Vacancies Interstitials + Phonons

Plasma-Wall Interaction Processes: Basic Processes II.) Physical sputtering Erosion yield Y: average number of eroded target atoms per incident projectile Impinging flux of projectiles : In general: definition of erosion yield YiEmitting flux of eroded particles : Erosion yield Y : number of incoming projectiles Γin = area time number of eroded particles Γero = Γarea time Yo= Γern

Plasma-Wall Interaction Processes: Basic Processes II.) Physical sputtering Main features of physical sputtering Occurs for all combinations of projectile substrate Existence of threshold energy E th. If E in < E th : Y sputter = 0 Sputter yield Y sputter depends on energy and angle of incoming projectile Sputter yield Y sputter depends on projectile material combination. Maximal energy transfer factor γ = 4 M 1 M 2 /(M 1 + M 2 ) 2 No significant dependence of Y sputter on surface temperature Sputtered species: atoms or small clusters of substrate particles

Plasma-Wall Interaction Processes: Basic Processes II.) Physical sputtering Typical dependence of sputter yield Y on incident energy of projectile H on Fe (normal incidence) Y E th ~ 8 ev E in [ev] E in < E th : Y = 0. Increasing E in Y increases until maximum. Further increase of E in Y decreases (collision cascade penetrates deeper into solid).

Plasma-Wall Interaction Processes: Basic Processes II.) Physical sputtering Typical dependence of sputter yield Y on incident angle of projectile H on Fe (E in = 200 ev) α in Y α in [ ] Y first increases with increasing α in (with grazing incidence more energy is deposited near surface). After reaching maximum Y decreases (reflection).

Plasma-Wall Interaction Processes: Basic Processes II.) Physical sputtering Energy distribution of sputtered particles Rare gas beam (45, 1 5keV) on Ag In many cases: sputtered particles have Thompson distributed energy N(E) E/(E + E S ) 3 E S : sublimation energy Most probable energy E = E S /2 E S /2 Deviations from Thompson distribution for light ion bombardment and/or nonnormal incidence

Plasma-Wall Interaction Processes: Basic Processes II.) Physical sputtering Angle distribution of sputtered particles N [a.u.] 1.0 30 330 0 30 30 0.8 α in 0.6 0.4 60 300 60 60 0.2 90 0.0 90 In many cases: sputtered particles have cosine distribution Deviations: for light ions and non-normal incidence

JET Divertor D Be TEXTOR limiter Physical sputtering : deuterium impact on different first wall materials Maxwellian energy distribution shifted by the sheath potential (3 kt e ): E in ~ 6-7 kt e D Mo largest physical sputter yields and low threshold for Be small yields and large threshold for high Z materials threshold for D impact D B D C D W Be C W 3 ev 8 ev 80 ev

Total erosion Yield of Graphite, Be and W by D impact D + For beryllium and tungsten theoretical and experimental curves overlap. Be C Carbon shows additional erosion, not dependent on impact energy. W CHEMICAL EROSION

III.) Chemical erosion

Plasma-Wall Interaction Processes III.) Chemical erosion Mechanism: formation of molecules from projectiles and solid atoms projectile D + or D 0 Penetration of D eroded hydrocarbon C x D y Formation of C x D y graphite Impinging deuterium penetrates into graphite and forms hydrocarbon molecule after thermalisation molecule diffuses through porosity to surface of the solid and desorbs

Plasma-Wall Interaction Processes III.) Chemical erosion Main features of chemical erosion Occurs only for special combinations of projectile substrate (most important: hydrogen on graphite, oxygen on graphite) No (or very low) threshold energy Strong dependence of erosion yield Y chem on surface temperature T surf Dependence of erosion yield Y chem on hydrogen content in solid Synergetic effects caused by energetic ions Sputtered species: molecules formed from projectile and substrate atoms

Plasma-Wall Interaction Processes III.) Chemical erosion Fusion research: Importance of chemical erosion of carbon-based materials Main disadvantage of carbon-based materials: - chemical erosion due to hydrogen & its isotopes even at lowest plasma T e - in a fusion reactor: tritium (T) as fuel erosion of C x T y molecules re-deposition of C x T y molecules leads to formation of T-containing layers. Amount of permitted radioactive T limited to 350g in ITER removal of T-containing layers necessary after having reached 350g Advantages of carbon-based materials: - no melting even under extremely high power loads (in ITER: 10 MW/m 2 ) - high sublimation temperature (~3800 C) therefore carbon-based materials are foreseen to use at areas of high power loads in ITER (divertor plates)

Plasma-Wall Interaction Processes III.) Chemical erosion of carbon-based materials Dependence of chemical erosion yield on surface temperature T surf 5 5 950 K 4 4 Methane Yield [%] 3 2 3 2 Maximum erosion yield @ ~950K Erosion yield decreases with elevated T surf 1 400 600 800 1000 1200 1400 T surf [K] 1

Plasma-Wall Interaction Processes III.) Chemical erosion of carbon-based materials Flux dependence of chemical erosion yield 10-1 Chemical Erosion Yield (at/ion) 10-2 Ion Beams IPP PSI1 JT-60U outer div ToreS 2001 ToreS 2002 TEXTOR PISCES JET 2001 Chemical erosion yield decreases with increasing deuterium flux 10-3 10 19 10 20 10 21 10 22 10 23 10 24 Ion Flux (m -2 s -1 )

III.) Chemical erosion of carbon-based materials Chemical erosion yield in dependence on properties of carbon material 1.E+00 more soft 1.E-01 1.E-01 Total Erosion Yield [C/H o or C/D o ] 1.E-02 1.E-03 H o on graphite D o on a-c:h hard 1000 1.E-02 1.E-03 a-c:h amorphous hydrocarbon layer Soft (hydrogen-rich) carbon layers suffer from an enhanced chemical erosion 1.E-04 1.E-04 H o on diamond films 1.E-05 200 400 600 800 1000 Temperature [K] 1.E-05

Plasma-Wall Interaction Processes III.) Chemical erosion of carbon-based materials N [a.u.] 4 3 2 1 Energy and angle distribution of eroded particles 300K 2000K Chemically eroded particles have Maxwell distributed energy (E ~ kt surf ~ 0.05 ev @RT) 0 0.0 0.1 0.2 0.3 0.4 0.5 E [ev] Angle distribution of chemically eroded molecules: as for physical sputtering: good choice cosine distribution

IV.) Radiation Enhanced Sublimation (RES)

Plasma-Wall Interaction Processes IV.) Radiation Enhanced Sublimation (RES) Erosion yield from beam experiments in dependence on surface temperatures 5 kev Ar + on graphite Ueda et al. For carbon-based materials: increasing erosion yield at surface temperatures larger than ~1000K radiation enhanced sublimation physical sputtering

Plasma-Wall Interaction Processes IV.) Radiation Enhanced Sublimation (RES) ion Mechanism of RES sublimated C graphite C interstitial impinging ion produces C interstitial C interstitial diffuses to surface and sublimes During diffusion of C interstitials to surface: probability of recombination with vacancies or stable defects ( annihilation of interstitial) Density of vacancies increases with increasing ion flux flux dependence of RES So far RES not clearly seen in tokamak experiments (not yet clarified)

V.) Backscattering

Plasma-Wall Interaction Processes V.) Backscattering Reflection of impinging particles at the surface incoming particle α in α out reflected particle R = Reflection coefficient R: amount of reflected particles amount of incoming particles solid Deposition = 1 - R In most cases: reflected particles are neutrals Reflection coefficient depends on: - mass of projectile and target - energy and angle of incident particles

Plasma-Wall Interaction Processes V.) Backscattering Dependency of reflection coefficient on incident energy Reflection coefficient R 0.20 0.15 Monte Carlo simulation (BCA): C on C, α in = 60 0.10 At low energies: BCA not valid Molecular Dynamic 0.05 calculations yield R 0 0.00 1 10 100 1000 Incident energy [ev]

Plasma-Wall Interaction Processes V.) Backscattering Dependency of reflection coefficient on incident angle Monte Carlo simulation (BCA): C on C, E in = 100 ev Reflection coefficient R 0.6 0.4 0.2 0.0 0 20 40 60 80 Incident angle α in [ C] α in

Plasma-Wall Interaction Processes V.) Backscattering Energy and angle distribution of reflected particles Reasonable assumptions: Energy: exponential decrease for reflected particles if incoming particle energy is Maxwell-distributed Angle: cosine distribution for reflected particles if isotropic bombardment

further important Plasma-Wall Interaction Processes

Plasma-Wall Interaction Processes VI.) Retention Hydrogen retention in graphite and co-deposited layers Licensing: in-vessel tritium inventory in ITER limited to 350g Four retention mechanisms have been identified: Build-up of a saturated surface layer during hydrogen implantation Chemisorption on grain boundaries and inner porosity surfaces Intergranular diffusion and trapping at temperatures > 1000K Co-deposition of hydrogen with carbon Based on experimental data: Co-deposition is expected to be most important mechanism for long-term tritium retention in ITER

Plasma-Wall Interaction Processes V.) Retention Hydrogen retention via co-deposition build-up of hydrogen containing layers D C x D y D C x D y + C X D y shadowed areas physical & chemical erosion yields: 1-3 % re-deposited carbon can be reeroded much stronger (10-20%)

Plasma-Wall Interaction Processes VII.) Adsorption/Desorption Definition of the processes Adsorption: binding of particles or molecules to a solid surface (adsorption from residual gas O 2, H 2 O, CO or from impurities segregated at surface at elevated temperatures) physisorption: binding due to van der Waals forces (E B <~0.5eV) chemisorption: binding via exchange/sharing of electrons (E B ~ ev) Desorption: adsorbed species leave the surface and return into gas phase impurity release process Ion-induced desorption most important desorption process for fusion.

Plasma-Wall Interaction Processes VIII.) Blistering Trapping of gas atoms in bubbles of high pressure Example: blistering in tungsten Pressure in bubble too high repetitive exfoliation of micron-thick flakes

Plasma-Wall Interaction Processes IX.) Secondary Electron Emission Mechanisms of secondary electron emission reflection of electrons which impinge the surface, mostly elastic scattering true electron-induced secondary electron emission from the solid ion-induced electron emission Why important in fusion research? Secondary electron emission coefficient influences the the sheath potential in front of target surface exposed to plasma (later in these lectures )

Detailed book-keeping of PWI processes (and local transport) The Impurity Transport Code ERO: see also: lecture III radial direction B background plasma incoming flux (D +, C 4+, O 5+ ) reflected and eroded particles C x+ CD y 0,+ reflected and eroded particles E C 0 deposition CD 4 re-deposition limiter-surface toroidal direction

Plasma wall interaction is unavoidable and necessary for particle and energy exhaust WHAT happens: Low Z materials are favourable since higher concentrations can be tolerated in the plasma due to lower radiation losses but the erosion of low Z materials is stronger. A compromise between impurity release and acceptable impurity concentration must be found, which is connected by impurity transport. Graphite has large advantages for off- normal heat loads in ELMS and disruptions, since it does not melt, but the disadvantage of high erosion and which can lead to large fuel retention by co-deposition High Z metals have much lower erosion and show much lower hydrogen retention but metal walls can suffer from melt layer loss in off normal heat loads. Next lecture: HOW can we make ITER work despite these issues